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Advanced Fuel CANDU Reactor Technical Summary Company Proÿle Advanced Fuel CANDU Reactor Technical Summary Company Proÿle SNC-Lavalin’s Nuclear team provides leading nuclear on four continents. CANDU technology provides safe, technology products and full-service solutions to reliable, affordable and CO2-free energy to support nuclear utilities around the globe. Our team of 1,200 the economic viability of businesses and quality of engineering, procurement, construction and project life for consumers in Canada, Romania, Korea, China management experts offer customized operations, and Argentina. CANDU reactors have an outstanding maintenance and plant life management services, performance record, taking four of the top ÿve places including waste management and decommissioning. on Nuclear Engineering International’s 2013 Top Our experts in nuclear steam plant and balance of Lifetime Performers List. plant engineering carry out life extension projects, and design and deliver state-of-the-art CANDU® reactors, Continuing a tradition of building nuclear reactors which are capable of operating on many types of fuel for over 50 years, we make signiÿcant contributions including natural uranium, recycled uranium (RU), to the nuclear energy ÿeld. CANDU technology is the thorium and mixed oxide (MOX) fuel. basis for Canada’s nuclear power program and has been adopted in the nuclear power programs of many We are the stewards of CANDU technology. The countries. The 11 CANDU 6 units, in ÿve countries, 47 heavy water reactors in operation or under life have consistently delivered an average lifetime extension are based on our CANDU design and are an capacity factor of over 87%. important component of clean air energy programs Noteworthy facts about the CANDU reactor łeet CANDU REACTORS CANDU BRAND CONSISTENTLY RANK IS RECOGNIZED AS ONE OF AS TOP PERFORMERS THE TOP 10 MAJOR AND HOLD THE WORLD RECORD FOR ENGINEERING ACHIEVEMENTS LONGEST CONTINUOUS OPERATION OF THE PAST CENTURY IN CANADA CANDU REACTORS CAN EXCELLENT BE EASILY ADAPTED FOR PERFORMANCE FLEXIBLE FUEL OF THE CANDU 6 FLEET WITH AN AVERAGE LIFETIME % CYCLE OPTIONS CAPACITY FACTOR OF OVER 87 CANDU REACTORS IN THE WORLD OPERABLE OR 31 BEING REFURBISHED Table of Contents Advanced Fuel CANDU Reactor ............................................................. 4 Safety Support Systems ................................................................................... 31 Safety in Depth.........................................................................................................4 Emergency Water Supply System ................................................................. 31 Proven..........................................................................................................................4 Raw Service Water and Recirculated Cooling Water Systems ........... 32 Economically Enabling the Fuel Cycle ............................................................4 Emergency Power Supply System................................................................. 32 CANDU: A Success Story ..........................................................................5 AFCR Plant Siting and Layout ............................................................... 33 Proven Delivery Track Record ............................................................................6 Reactor Building ...................................................................................................35 Development of AFCR Technology ...................................................................6 Service Building ....................................................................................................36 Technical Description of the AFCR .........................................................8 Turbine Building ....................................................................................................36 High Level Design Speciÿcations ......................................................................8 Nuclear Systems ...................................................................................... 37 Main Characteristics of the AFCR .....................................................................8 Heat Transport System......................................................................................38 AFCR Advantages for Advanced Fuel Cycles ....................................11 Steam Generators ................................................................................................39 Fuel .............................................................................................................................12 Heat Transport System Pumps ......................................................................39 Direct use of Recycled Uranium Fuel ............................................................12 Heat Transport Pressure and Inventory Control System ......................40 Low-Enriched Uranium (LEU) and Thorium (Th) Fuel ............................ 13 Moderator System ...............................................................................................40 Economic Value Using Advanced Fuel Cycles ........................................... 13 Reactor Assembly ................................................................................................ 41 Safety is at Our Core .............................................................................. 14 Reactor Power Control .......................................................................................42 AFCR Safety Design Philosophy ..................................................................... 14 Fuel Channel Assembly .....................................................................................42 AFCR Safety Goals .............................................................................................. 15 Fuel Handling and Storage System ...............................................................43 Defence-in-Depth ................................................................................................. 15 Turbine-Generator System ....................................................................44 Designed Based on Post-Fukushima Requirements ................................17 Turbine Generators ..............................................................................................44 AFCR Fundamental Safety Function Features ........................................ 18 Main Steam System ............................................................................................44 Reactivity Control ................................................................................................ 19 Condensing System.............................................................................................45 Fuel Cooling ...........................................................................................................20 Condensate and Feedwater System .............................................................45 Spent Fuel Cooling .............................................................................................. 22 Instrumentation and Control .................................................................46 Containment .......................................................................................................... 23 AFCR Control Centres ........................................................................................47 Reliable and Robust Design .................................................................. 24 Reactor Regulating System ..............................................................................49 Fail Safe Design ....................................................................................................24 Reactor Safety Instrumentation .....................................................................49 Single Failure Criterion .......................................................................................24 Safety Monitoring .................................................................................................49 Diversity ...................................................................................................................24 Electrical Power System ........................................................................50 Reliability .................................................................................................................24 Conventional Plant Services ................................................................. 51 Grouping and Separation ................................................................................... 25 Service Water Systems ...................................................................................... 51 Seismic Qualiÿcation .......................................................................................... 25 Heating, Ventilation and Cooling Systems .................................................. 51 Environmental Qualiÿcation............................................................................. 25 Fire Protection System....................................................................................... 51 Ageing ....................................................................................................................... 25 Radioactive Waste Management .......................................................... 52 Radiation Protection ............................................................................................ 26 Modular Air-Cooled Storage (MACSTOR) ..................................................
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